WO2006099643A1 - Composant de premiere paroi pour un reacteur de fusion - Google Patents

Composant de premiere paroi pour un reacteur de fusion Download PDF

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Publication number
WO2006099643A1
WO2006099643A1 PCT/AT2006/000113 AT2006000113W WO2006099643A1 WO 2006099643 A1 WO2006099643 A1 WO 2006099643A1 AT 2006000113 W AT2006000113 W AT 2006000113W WO 2006099643 A1 WO2006099643 A1 WO 2006099643A1
Authority
WO
WIPO (PCT)
Prior art keywords
wall component
slot
heat shield
cooling tube
component
Prior art date
Application number
PCT/AT2006/000113
Other languages
German (de)
English (en)
Inventor
Thomas Friedrich
Arno Plankensteiner
Bertram Schedler
Karlheinz Scheiber
Hans-Dieter Friedle
Thomas Huber
Dietmar Schedle
Anton Zabernig
Original Assignee
Plansee Se
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Plansee Se filed Critical Plansee Se
Priority to AU2006227582A priority Critical patent/AU2006227582B2/en
Priority to JP2008502182A priority patent/JP5329219B2/ja
Priority to EP06704755.5A priority patent/EP1861855B1/fr
Priority to KR1020077020719A priority patent/KR101242871B1/ko
Priority to BRPI0609128-8A priority patent/BRPI0609128B1/pt
Priority to CA2600187A priority patent/CA2600187C/fr
Publication of WO2006099643A1 publication Critical patent/WO2006099643A1/fr
Priority to US11/859,993 priority patent/US8064563B2/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21B—FUSION REACTORS
    • G21B1/00—Thermonuclear fusion reactors
    • G21B1/11—Details
    • G21B1/13—First wall; Blanket; Divertor
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/10—Nuclear fusion reactors

Definitions

  • the invention relates to a first-wall component of a fusion reactor, the at least one heat shield with a closed or open implementation of a graphite material and a coolant through which at least partially cohesively connected heat pipe made of a material having a thermal conductivity> 200 W / m- K includes.
  • First wall components typically consist of a heat shield and a heat dissipating area.
  • the material of the heat shield must be compatible with the plasma, have a high resistance to physical and chemical sputtering, have a high melting point / sublimation point and be as resistant to thermal shock as possible. In addition, they must still have a high thermal conductivity, low neutron activability and sufficient strength / fracture toughness, with good availability and acceptable costs.
  • graphite materials eg fiber-reinforced graphite
  • first-wall components are typically actively cooled.
  • the heat dissipation is supported by heat sinks, such as copper or copper alloys, which are usually positively connected to the heat shield.
  • First wall components can be designed with different designs.
  • a common design is the so-called monobloc design.
  • the first wall component consists of a heat shield with a concentric bore. About this concentric bore of the heat shield is connected to the cooling tube.
  • First-wall components must withstand not only thermally induced but also additional mechanical stresses. Such Additional mechanical loads may be generated via electromagnetically induced currents that flow in the components and interact with the magnetic field of the environment. This high-frequency acceleration forces can occur, which must be transferred from the heat shield, so for example, the graphite material.
  • graphitic materials have low mechanical strength and fracture toughness.
  • neutron embrittlement occurs during use, further increasing the sensitivity of these materials to crack initiation.
  • Fiber-reinforced graphite (CFC) is usually used as the graphic material. The fiber reinforcement is arranged three-dimensionally and linearly. The architecture of the fibers gives the material different properties depending on the spatial direction. CFC is usually reinforced in one spatial direction by ex-pitch fibers that have both the highest strength and thermal conductivity. The other two spatial directions are reinforced by Ex-PAN fibers, with one direction typically only needled.
  • connection geometry heat shield / cooling tube is circular. Due to the different thermal expansion coefficients of the materials used, a build-up of stress occurs in the manufacturing process, which can lead to cracks in the CFC. Due to the geometric conditions and the material combination used, these cracks can only be detected, if at all, with very complex methods. This raises corresponding problems against the background of a nuclear environment for such components, above all because cracks / detachments are seen as a possible trigger for a major accident. Despite years of extensive development work in the field of first-wall components, the components that have been available to date do not optimally fulfill the requirement profile.
  • the object of the invention is therefore to provide a first-wall component which satisfies the requirements resulting from mechanical stresses in a suitable manner. This problem is solved according to the features of claim 1.
  • the first-wall component comprises at least one heat shield made of a graphite material with a plasma-inclined surface A and a surface B facing thereto.
  • the heat shield has one or more slits which open into the surface A or B and, in the direction of Viewed axis of the cooling tube, run substantially the length of the heat shield. It is further advantageous that the maximum slot width in the region of the slot bottom D / 2 does not exceed, where D is the outer diameter of the cooling tube.
  • the slot depth is advantageously greater than half the distance between A and B and the nearest surface of the cooling tube.
  • a particularly favorable range for the slot depth x is u / 2 ⁇ x ⁇ 9u / 10, where u is the distance measured in the vertical direction between the area A or B and the nearest cooling tube surface.
  • the slot may also extend to the cooling tube or to a ductile layer surrounding the cooling tube.
  • the heat shield has no closed, but an open passage. Since cooling tubes with a circular cross section are usually used, the bushing also has a circular cross section.
  • the minimum slot width of 10 ⁇ m results from the cutting methods available for graphitic materials, such as diamond sawing or wire cutting.
  • the preferred maximum slot width is D / 3.
  • Thermal conductivity is the use of copper alloys for the cooling tubes to prefer.
  • the stresses in the component can be further reduced by the introduction of a very soft layer (hardness ⁇ 200 HV) between the cooling tube and the heat shield.
  • the invention is illustrated and explained by way of example by FIGS. 1 to 7 and the examples below.
  • FIG. 1 shows an oblique view of a component according to the invention with a slot.
  • FIG. 2 shows the elevational view of the component according to FIG. 1
  • FIG. 3 shows the cross section of the component according to FIG. 1 and further the CFC fiber direction.
  • FIG. 4 shows an oblique view of a component according to the invention with two slots.
  • FIG. 5 shows the elevational view of the component according to FIG.
  • Figure 6 shows the cross section of the component according to Figure 4 and further the CFC fiber direction
  • Figure 7 shows the elevation of a component according to the invention with a V-shaped slot
  • a first wall component -1 - according to FIGS. 1 to 3 was produced as follows:
  • Heat shields -2- in the form of monoblocks with a hole -4- were made of fiber-reinforced graphite blocks (CFC), with the high-strength ex-pitch fibers in the direction of highest thermal conductivity, the Ex-PAN fibers parallel to the axis of the cooling tube and the needled Ex -PAN fibers were in the cooling tube axis.
  • the dimensions of the individual monoblocks were 40 mm (Ex-Pitch), 30 mm (Ex-PAN) and 20 mm (Ex-PAN Needled).
  • the diameter of the hole -4- was 14 mm and was located in the symmetry center -9- of the heat shield -2-.
  • the wall of hole -4- was patterned by LASER, thereby introducing a multiplicity of tapered holes into the CFC.
  • such holes typically have a depth of about 0.5 mm and an opening on the surface of 0.2 - 0.3 mm. The distance was chosen to maximize the surface of the bore wall.
  • a slit -7- with a slit width of 0.3 mm was inserted in the heat shield -2- by means of wire cutting. This slot -7- was in the axis of symmetry of the heat shield -2- and ran from the plasma-remote surface -6- to the centrally located hole -4-.
  • the bore -4- was poured via a casting process in the presence of a carbide such as titanium with oxygen-free copper.
  • a carbide such as titanium with oxygen-free copper.
  • the process was carried out so that the previously introduced 0.3 mm wide slot -7- in the heat shield -2- was not wetted by copper during this Gréreas.
  • the flanks of the slot -7- have a smaller distance compared to the processing state. This circumstance showed that the occurring stresses were converted into deformation. This led to a reduction in stress, without the functionality and the favorable properties of the component -1- were lost by this measure.
  • a visual and metallographic assessment of the CFC / Cu interface in the back-cast state revealed no evidence of possible delamination in the CFC / copper composite.
  • the resulting copper-filled bore -4- was then subjected to mechanical machining, so that a bore with a diameter of 12.5 mm and thus an approximately 0.5 - 1, 0 mm thick copper layer remained on the CFC.
  • Three heat shields -2- with slit -7- thus obtained were threaded on a cooling tube -3 of CuCrZr alloy having a diameter of 12 mm and inserted into a metallic can. After welding the pot, it was evacuated and then the suction nozzle sealed vacuum-tight. The so-called components were then one HIP process at 55O 0 C and 1000 bar subjected.
  • First wall component -1 - removed. A visual assessment did not reveal any errors, such as delaminations. An additional ultrasonic test with an inner tube probe showed a perfect interface. Finally, this first wall component -1 - was subjected to the plasma of a VPS plant. Component -1- was connected to the cooling water system in the system and held by the gripper arm of the robot installed in the system. By means of the flow velocity, the temperature increase of the cooling medium and the surface acted upon by the plasma, a heat flow in the range of 10-15 MW / m 2 was determined. Overall, component -1 was cycled about 100x by moving through the plasma. When moving, the component -1- was held in the plasma until the temperature of the cooling water did not continue to warm. After this test, the component -1 - was tested destructive. It was found that none of the investigated heat shields -2 could detect a crack, a circumstance which could not yet be achieved with components not according to the invention.
  • Example 2 A further component -1- was produced according to Example 1. In the subsequent test, the slotted surface was exposed to the plasma. The test gave similar results as in Example 1, with the difference that in the area of the slot -7- a slight erosion took place.
  • a first wall component -1 - according to FIGS. 1 to 3 was produced as follows: Heat shields -2- in the form of monoblocks with a hole -4- were made out of fiber-reinforced graphite blocks (CFC), again with the high-strength ex-pitch fibers in the direction of highest thermal conductivity, the ex-PAN fibers parallel to the axis of the cooling tube and the needled Ex-PAN fibers lay in the cooling tube axis.
  • the dimensions of the individual monoblocks corresponded to those of Example 1.
  • the introduction of the bore and the laser structuring were carried out as described in Example 1.
  • a slit -7- with a slit width of 0.3 mm was inserted in the heat shield -2- by means of wire cutting.
  • This slot -7- lay on the symmetry axis of the heat shield -2- and broke through the hole -A-.
  • the bore -A- analogous to Example 1 was poured with oxygen-free copper, subjected to mechanical processing, connected to a cooling tube -3- of a CuCrZr alloy by means of soldering, the brazing temperature in the range of solution annealing temperature (970 ° C) of CuCrZr was.
  • the cooling from soldering temperature to below 400 0 C was carried out at a cooling rate> 1 K / sec, which could be set in a subsequent aging at 475 ° C / 3h optimum strength values.
  • the composites produced in this way also showed no cracks after the thermal cycling according to Example 1.
  • a first wall component -1- according to FIGS. 4 to 6 was produced as follows:
  • Heat shields -2- in the form of monoblocks with a hole -4- were made out of fiber-reinforced graphite blocks (CFC), again with the high-strength ex-pitch fibers in the direction of highest thermal conductivity, the ex-PAN fibers parallel to the axis of the cooling tube and the needled Ex-PAN fibers lay in the cooling tube axis.
  • CFC fiber-reinforced graphite blocks
  • the dimensions of the individual monoblocks corresponded to those of Example 1.
  • the introduction of the bore and the laser structuring were carried out as described in Example 1.
  • two slits -7- with a slit width of 0.3 mm in the heat shield -2- was introduced by wire cutting.
  • These slits -7- were mirror images of the symmetry axis of the heat shield -2-.
  • the slits -7- each had a depth x of 0.8 u, where u is the smallest Distance between the heat shield surface -5- and the cooling pipe -3- is.
  • the hole -4- was poured analogously to Example 1 with oxygen-free copper, subjected to mechanical processing, with a cooling tube -3- from a CuCrZr alloy by means of soldering according to the sequence in Example 3 materially connected.
  • the composites produced in this way also showed no cracks after the thermal cycling according to Example 1.
  • a first wall component -1 - according to FIG. 7 was produced as follows: Monoblocks were produced in accordance with Example 1. On the side facing away from the plasma, a V-shaped slot -7-, as shown in Figure 7 was introduced by means of wire cutting. The further production steps were carried out as described in Example 1. The composites produced in this way also showed no cracks after the thermal cycling according to Example 1.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Arc Welding In General (AREA)
  • Coating By Spraying Or Casting (AREA)
  • Ceramic Products (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Cooling Or The Like Of Semiconductors Or Solid State Devices (AREA)
  • Cooling Or The Like Of Electrical Apparatus (AREA)

Abstract

Composant de première paroi pour un réacteur de fusion, qui comporte au moins un bouclier thermique possédant une zone A orientée vers le plasma et une zone B opposée à la zone A et constituée d'une matière graphitique. Le bouclier thermique possède une ou plusieurs fentes qui débouchent sur les surfaces A et B et sont orientées essentiellement en direction de l'axe du tube de refroidissement. Les composants répondent de manière adaptée aux sollicitations mécaniques résultant de la fabrication ainsi que des cycles thermiques.
PCT/AT2006/000113 2005-03-22 2006-03-17 Composant de premiere paroi pour un reacteur de fusion WO2006099643A1 (fr)

Priority Applications (7)

Application Number Priority Date Filing Date Title
AU2006227582A AU2006227582B2 (en) 2005-03-22 2006-03-17 First wall components for a fusion reactor
JP2008502182A JP5329219B2 (ja) 2005-03-22 2006-03-17 核融合炉用の第一壁構成部材
EP06704755.5A EP1861855B1 (fr) 2005-03-22 2006-03-17 Composant de premiere paroi pour un reacteur de fusion
KR1020077020719A KR101242871B1 (ko) 2005-03-22 2006-03-17 핵융합로용 제1벽 부품
BRPI0609128-8A BRPI0609128B1 (pt) 2005-03-22 2006-03-17 Primeiro componente de parede para reator de fusão
CA2600187A CA2600187C (fr) 2005-03-22 2006-03-17 Composant de premiere paroi pour un reacteur de fusion
US11/859,993 US8064563B2 (en) 2005-03-22 2007-09-24 First-wall component for a fusion reactor

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
ATGM179/2005 2005-03-22
AT0017905U AT8485U1 (de) 2005-03-22 2005-03-22 Erste-wand-komponente für fusionsreaktor

Related Child Applications (1)

Application Number Title Priority Date Filing Date
US11/859,993 Continuation US8064563B2 (en) 2005-03-22 2007-09-24 First-wall component for a fusion reactor

Publications (1)

Publication Number Publication Date
WO2006099643A1 true WO2006099643A1 (fr) 2006-09-28

Family

ID=36578782

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/AT2006/000113 WO2006099643A1 (fr) 2005-03-22 2006-03-17 Composant de premiere paroi pour un reacteur de fusion

Country Status (11)

Country Link
US (1) US8064563B2 (fr)
EP (1) EP1861855B1 (fr)
JP (1) JP5329219B2 (fr)
KR (1) KR101242871B1 (fr)
CN (1) CN101147207A (fr)
AT (1) AT8485U1 (fr)
AU (1) AU2006227582B2 (fr)
BR (1) BRPI0609128B1 (fr)
CA (1) CA2600187C (fr)
RU (1) RU2399966C2 (fr)
WO (1) WO2006099643A1 (fr)

Cited By (1)

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JP2009192264A (ja) * 2008-02-12 2009-08-27 Kawasaki Plant Systems Ltd 炭素材と銅合金材を冶金的に接合する高熱負荷機器製造方法

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CN102222528B (zh) * 2011-04-11 2013-02-13 核工业西南物理研究院 第一镜样品辐照支架与辐照方法
CN102284837B (zh) * 2011-07-07 2013-06-26 中国科学院等离子体物理研究所 一种用于核聚变装置的高热负荷部件制造方法
FR2978860A1 (fr) * 2011-08-01 2013-02-08 Commissariat Energie Atomique Composant de premiere paroi pour reacteur de fusion nucleaire et son procede de realisation
RU2484545C1 (ru) * 2011-11-30 2013-06-10 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Система для пневматической транспортировки тритийвоспроизводящих детекторов в канале наработки трития бланкета термоядерного реактора
CN102564831B (zh) * 2011-12-07 2014-05-07 中国科学院等离子体物理研究所 用于核聚变实验装置的第一壁部件上可拆卸分析的嵌入式样品装夹方法
JP6173767B2 (ja) * 2013-05-16 2017-08-02 川崎重工業株式会社 炭素繊維複合材料製受熱タイルおよびその製造方法
JP6403040B2 (ja) 2014-02-05 2018-10-10 川崎重工業株式会社 炭素繊維複合材製受熱タイルおよびその製造方法
US9992917B2 (en) 2014-03-10 2018-06-05 Vulcan GMS 3-D printing method for producing tungsten-based shielding parts
CN103886919B (zh) * 2014-03-26 2016-02-17 北京工业大学 利用叠片结构提高聚变堆内壁耐等离子体辐照性能的方法
CN105989902B (zh) * 2015-12-23 2018-11-13 中国科学院等离子体物理研究所 一种用于核聚变装置城堡形部件结构研究的样品设计方法
CN108269622A (zh) * 2016-12-30 2018-07-10 核工业西南物理研究院 一种被动冷却式托克马克装置弱场侧第一壁组件
CN109961856A (zh) * 2017-12-25 2019-07-02 哈尔滨工业大学 一种防止直面等离子体部分温度过高的核聚变第一壁
CN111312411B (zh) * 2018-12-11 2022-10-21 核工业西南物理研究院 液化惰性气体射流注入防护等离子体破裂的方法
CN110047599A (zh) * 2019-03-21 2019-07-23 中国科学院合肥物质科学研究院 一种用于聚变装置冷屏的绝缘结构
CN111826609B (zh) * 2020-03-30 2022-06-28 中国工程物理研究院激光聚变研究中心 一种u-w-n三元薄膜及其制备方法和应用
CN111477352B (zh) * 2020-04-22 2023-03-10 中国科学院合肥物质科学研究院 一种用于聚变装置偏滤器第一壁相邻冷却通道的u型装置及其装配方法
GB202018198D0 (en) 2020-11-19 2021-01-06 Tokamak Energy Ltd Breeder blanket
CN112743298B (zh) * 2020-12-29 2023-02-14 武汉善福重型机床有限公司 一种冷却系统热屏蔽模块的制造方法
CN112992384A (zh) * 2021-02-07 2021-06-18 中国科学院合肥物质科学研究院 一种碳纤维增强复合材料cfc保护限制器
CN114864113B (zh) * 2022-05-31 2023-03-14 核工业西南物理研究院 一种托卡马克第一壁结构

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US20040195296A1 (en) * 2003-04-02 2004-10-07 Bertram Schedler Composite component for fusion reactors

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009192264A (ja) * 2008-02-12 2009-08-27 Kawasaki Plant Systems Ltd 炭素材と銅合金材を冶金的に接合する高熱負荷機器製造方法

Also Published As

Publication number Publication date
AT8485U1 (de) 2006-08-15
CN101147207A (zh) 2008-03-19
CA2600187A1 (fr) 2006-09-28
EP1861855B1 (fr) 2015-08-26
AU2006227582B2 (en) 2012-02-02
CA2600187C (fr) 2012-10-16
RU2399966C2 (ru) 2010-09-20
AU2006227582A1 (en) 2006-09-28
US20080032530A1 (en) 2008-02-07
US8064563B2 (en) 2011-11-22
JP5329219B2 (ja) 2013-10-30
BRPI0609128A2 (pt) 2010-02-23
EP1861855A1 (fr) 2007-12-05
KR101242871B1 (ko) 2013-03-12
KR20070113219A (ko) 2007-11-28
BRPI0609128B1 (pt) 2018-01-09
JP2008533492A (ja) 2008-08-21
RU2007135120A (ru) 2009-04-27

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